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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
IAEA again raises global nuclear power projections
Noting recent momentum behind nuclear power, the International Atomic Energy Agency has revised up its projections for the expansion of nuclear power, estimating that global nuclear operational capacity will more than double by 2050—reaching 2.6 times the 2024 level—with small modular reactors expected to play a pivotal role in this high-case scenario.
IAEA director general Rafael Mariano Grossi announced the new projections, contained in the annual report Energy, Electricity, and Nuclear Power Estimates for the Period up to 2050 at the 69th IAEA General Conference in Vienna.
In the report’s high-case scenario, nuclear electrical generating capacity is projected to increase to from 377 GW at the end of 2024 to 992 GW by 2050. In a low-case scenario, capacity rises 50 percent, compared with 2024, to 561 GW. SMRs are projected to account for 24 percent of the new capacity added in the high case and for 5 percent in the low case.
Jan-Ru Tang, Lainsu Kao, Der-Yeong Shiau, Lin-Yao Chou, Ching-Chuan Yao, Show-Chyuan Chiang
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 302-312
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2842
Articles are hosted by Taylor and Francis Online.
Two analyses for Chinshan nuclear power station (CSNPS) show the RETRAN applications in reactor operations. One was used to find the root cause of a reactor trip due to high neutron flux (APRM Hi-Hi). Two of the four turbine control valves failed and closed rapidly. Whether the pressure increase caused the APRM Hi-Hi reactor scram was questioned. An analysis was performed to determine the way to bring unit 1 back to power. The second analysis was conducted to provide an evaluation of the consequences before a plant test planned for late 1994 to consider a design change upgrading recirculation flow control. However, there were concerns about reactor scram during execution of the test and the potential of entering the exclusive region of instability. Sensitivity studies on several different combinations of initial conditions and feedwater flow coastdown curves indicated potential problems with reactor trip and stability.
